New Challenges in Safety Analysis of Nuclear Reactors
A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".
Deadline for manuscript submissions: 20 February 2025 | Viewed by 102
Special Issue Editors
Interests: nuclear energy; nuclear power instrumentation; control and operation; nonlinear control; high temperature gas-cooled reactor
Special Issues, Collections and Topics in MDPI journals
Interests: nuclear energy; nuclear reactor thermal-hydraulics; nuclear safety analysis; high temperatrure gas-cooled reactor
Interests: nuclear energy; probability safety analysis; high temperature gas-cooled reactor
Special Issue Information
Dear Colleagues,
Nuclear fission energy is a firm low-carbon resource for fighting against climate change, and is suitable to be adopted as the energy source for those difficult-to-decarbonize industrial sectors, including long-distance transportation; shipping; the production of carbon-intensive materials such as steel and cement; the provision of reliable and flexible electricity supply, etc. The three severe nuclear accidents, i.e., the Three Mile Island accident, the Chernobyl accident, and the Fukushima Daiichi accident, indicate that strictly guaranteeing safety is a prerequisite of large-scale deployment and public acceptance of nuclear power. To enhance the safety level of nuclear power plants, extensive research and development (R&D) efforts have been completed on nuclear safety, resulting in a series of remarkable and exciting advances of nuclear power technology, such as the 3rd generation nuclear power plants AP1000 and HPR1000, equipped with a passive decay heat-removing system, as well as the inherently safe modular high temperature gas-cooled reactor nuclear power plant HTR-PM, commercially operated since 6 December 2023. Nowadays, given the increasing requirements for multiple unit/modular nuclear power generation and cogeneration, deep load following, flat digital control system, etc., nuclear safety analysis faces some new challenges. Currently, nuclear safety analysis is not only achieved by reactor accident analysis and probability safety analysis (PSA), but also relates to issues such as deep load following, nuclear security, equipment performance, and reliability. These new challenges indicate the intention of arranging this Special Issue.
The topics of this Special Issue on “New challenges in Safety Analysis of Nuclear Reactors” include, but are not limited to, the following:
- Accident analysis,
- Probability safety analysis (PSA),
- Nuclear security,
- Digital protection system and safety-level instrumentation,
- Nuclear power plant control method for enhancing operational stability and reliability,
- Application of artificial intelligence in nuclear safety analysis, control, and monitoring,
- Modeling and simulation for safety analysis.
Dr. Zhe Dong
Prof. Dr. Yanhua Zheng
Dr. Jun Zhao
Dr. Jianghai Li
Guest Editors
Manuscript Submission Information
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Keywords
- nuclear energy
- nuclear safety
- nuclear security
- instrumentation and control
- operation monitoring
- artificial intelligence
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Planned Papers
The below list represents only planned manuscripts. Some of these manuscripts have not been received by the Editorial Office yet. Papers submitted to MDPI journals are subject to peer-review.
Title: Multi-agent reinforcement learning-based coordination control optimization for a nuclear steam supply system
Authors: Tianhao Zhang
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Common cause failure assessment in the requirements phase of safety critical software development for nuclear power plants
Authors: Boyuan Li
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Multivariate Time Series Reconstruction based Cyberattack Detection for the Control System of Multiple Modular High-Temperature Gas-Cooled Reactor
Authors: Zijian Wu
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Resilience Enhancement Based on Control Application Dynamic Configuration for the Control System of Multiple Modular High-Temperature Gas-Cooled Reactor
Authors: Zijian Wu
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Modeling and Coordinated Control of Modular High Temperature Gas-cooled Nuclear Power Generation and Hydrogen Cogeneration
Authors: Junyi Li
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Heat transfer coefficient estimation of shell-tube heat exchanger using recursive least squares method
Authors: Zhonghua Cheng
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Design and Verification of Reactor-Following-Load Coordinated Control Strategy for Modular High Temperature Gas-cooled Reactor
Authors: Xuan Li
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Improved Dynamic Matrix Control for Cold Helium Temperature of MHTGR Plants Based on Singular Value Decomposition
Authors: ZhenDong Wu
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Deep Neural Network Accident Transient Identification of Modular High Temperature Gas-Cooled Reactor
Authors: Jitao Li
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
Title: Alarm fluctuation suppressing though reactivity observation
Authors: Jize Guo
Affiliation: Institute of Nuclear and New Energy Technology, Tsinghua University, China
